IR 05000270/1973011
| ML19317D323 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/07/1973 |
| From: | Jape F, Murphy C, Whitt K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317D320 | List: |
| References | |
| 50-270-73-11, NUDOCS 7911270551 | |
| Download: ML19317D323 (15) | |
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UNITED STATES
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DIRECTOPATE OF REGUIATCRY CPIPATICNS
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AT L ANT A. GeoaGI A 30303 RO Innpection Report No. 50-270/73-11 Licensee: Duke Power Company Power Building 422 South Church Street Charlotte, North Carolina 28201 i
Facility: Oconee Unit 2 Docket No. : 50-270 License No.:
CPPR-34 Category: B1 Location:
Seneca, South Carolina
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Type of License: B&W, PWR, 2568 Mw(t)
Type of Inspecticn: Routine, Unannounced Dates of Inspection: August 28-31, 1973 Principal Inspector:
F. Jape, Reactor Inspector Facilities Test and Startup Branch Accompanying Inspectors:
K. W. Whitt, Reactor Inspector Facilities Test and Startup Branch.
R. C. Lewis, Reactor Inspector Facilities Operations Branch Other Accompanying Personnel:
W. C. Seidle, Chief
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Facilities Operations Branch
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Principal Inspector:
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F. Jape, Reactor Inspector Date
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Facilities Test and Startup Branch f/fjkJ Reviewed By:
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'C. E. Murphy 7 Cldef /
D4te Facilities Test and/Startup Branch en
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RO P.pt. No. 50-269/73-9-2-SUMMARY OF FINDINGS I.
Enforcement Action e
J A.
Violations None B.
Safety Items None II. Licensee Action on Previously Identified Enforcement Matters A.
Violations 1.
Welding Program Deficiencies (RO:II Letter to DPC, dated March 8, 1972, Item 5)
The licensee's report on welding deficiencies and documenta-tion has not yet been made available to RO for review. This item remains open.
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2.
Loss of Test Control (RO:II Lett6r to DPC, dated Augus t 29, 1973)
The licensee's response on this item is due on September 18, 1973.
This item will remain open until the response has been received and a followup inspection has been completed.
B.
Safety Items
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There are no previously identified safety items.
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III. New Unresolved Itens 73-11/1 Source Range Instrumentation Response
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Planned changes are underway and are to be completed prior to initial fuel loading.
(Details I, paragraph 5)
73-11/2 Electrical Interlock and Bypass Procedure An audit by the station QA group revealed a deficiency in following the procedure. Corrective measures were underway but had not been completed at the close of the inspection.
(Details II, paragraph 4.a.)
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[D RO Rpt. No. 50-269/73-9-3-
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IV.
Status of Previously Reported Unresolved ~ Items 73-10/1 Administrative Procedures This item was identified during the preceeding inspection and action by the licensee was not inspected during the current inspection. The licensee has indicated that the three additional administrative procedures or instructions would be provided by September 20, 1973.
73-8/2 Valve Wall Thickness of valve 2-RV-67 Calculation of valve wall thickness of valve 2-RV-67 in accordance with the applicable codes remains to be resolved.
73-8/1 Body Wall Thickness of Valves 2-51-244 and 2-51-245 Justification for body wall thickness of valves 2-51-244
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and 2-51-245 being less than that permitted by RO letter, dated June 30, 1972, paragraph 3, remains to be resolved.
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V.
Unusual Occurrences None VI.
Other Significant Findings Initial Fuel Loading Date The date for initial fuel loading has been moved from September 18, 1973, to October 7, 1973. Delays in completing the hot functional testing program on schedule is the reason for the change of date.
VII. Mana gement Interview A management interview was held on August 17, 1973, with the
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following in attendance:
Duke Power Company (DPC)
J. W. Hampton - Assistant Plant Superintendent J. W. Cox - Assistant Plant Engineer R. M. Koehler,- Technical Support Engineer D. C. Holt - Assistant Nuclear Test Engineer i3
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RO Rpt. No. 50-269/73-9-4-The following items were discussed:
A.
Miscellaneous Testg
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The inspector stated that he had reviewed miscellaneous
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tests performed on Unit 2 and found that the licensee had reviewed these tests and changed three to " Test Procedure" status. The inspector had no further comment or question on these tests.
(Details I, paragraph 2)
B.
Station Modifications The inspector stated that the method for handling stacion modifications aas reviewed. The licensee's representative indicated that the current method is an interim =easure and that a revist.d method for handling modifications is being developed.
(Details I, paragraph 3)
C.
Review of Test Procedures and Test Results
i The inspector stated thee four test procedures and the results from these procedures were reviewed.
There were no major questions
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or comments. However, one general coccent concerning verifica-tion and reverification of prerequisites and other test prepara-tion was discussed.
(Details I, paragraph 4 and Details II, paragraph 3)
D.
Source Range Instrumentation Response The modifications planned for the source range instrumentation were discussed.
The licensee representatives stated that these changes will be completed prior to initial fuel loading.
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E.
Witness of Tests
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The inspector stated that he had witnessed the performance of parts of two hot functional tests during the inspection and that no deficiencies had been noted.
(Details II, paragraph 2)
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F.
Station Quality Assurance Staff The inspector summarized his review of the audit records of the station quality assurance staff, and said the program appeared to be functioning in an effective manner.
He explained
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that the quality assurance audits indicated that some amount of trouble was being encountered in implementing certain pro-cedures. This appeared to be particularly true for control of j
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jumpers and bypasses and control of the tagging process.
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(Details II, paragraph 4)
G.
Steam Production Department Quality Assurance Staff The inspector stated that he had reviewed the available records of the steam production department quality assurance audits and summarized his findings.
(Details II, paragraph 5)
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Station Review Committee
i The minutes of the Station Review Committee were examined by
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the inspector. There were no major questions or comments.
(Details III, paragraph 3)
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Nuclear Safety Review Committee The minutes of the Nuclear Safety Review Committee were examined
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by the inspector. There were no major questions or comments.
(Details III, paragraph 4)
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i RO Rpt. No. 50-270/73-1 I-1
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- /~ d ~73 DETAILS I Prepared By:
F. Jape, Readtor' Inspector Date Facilities Test and Startup Branch Dates of Inspection:
Au ust 29-31,1973 Reviewed By-f
C. E. Mubphy', Chfef tate Facilities Test and Startup Branch 1.
Individuals Contacted Duke Power Company (DPC)
J. E. Smith - Plant Superintendent
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b J. W. Hampton - Assistant Plant Superintendent
R. M. Koehler - Technical Support Engineer
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L. E. Schmid - Operating Engineer L. E. Summerlin - Staff Engineer J. W. Cox - Assistant Plant Engineer D. J. Rains - Assistant Plant Engineer R. J. Brackett - Junior Engineer 2.
Miscellaneous Tests The use of miscellaneous tests was reviewed by the inspector. To date, nine miscellaneous tests have been performed. A feview, by the licensee, revealed that three of these tests were on safety related systems and should have been handled as test procedures (TP).
The inspector found that these three had been changed to TP's and have i
received the reviews and approvals required for TP's.
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The inspector also reviewed an intersation letter, dated June 22, 1973, issued bv the plant superintendent to supervisors and test coordinators.
The letter emphasized that safety related test procedures must be reviewed and approved according to Sections 4.3 and 4.4 of the Administrative Policy Manual for Operational Quality Assurance of Nuclear Stations (APM/NS).
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R0 Rpt. No. 50-270/73-1 I-2 i
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3.
Review of Station Modifications The method for handling station modifications was reviewed with licensee representatives.
The method is currently being revised in answer to questions and comments from RO:II during a recent audit 1/ on Oconee 1.
During the interim period, a track sheet is being used to ensure all reviews and appropriate approvals are received.
Three modifications, currently being handled by the interim method, were selected by the inspector for review. The inspector found that each modification was receiving the reviews and approvals required by the procedure. There were no deficiences nor comments on the handling procedure.
4.
Review of Test Procedures and Test Results i
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The following TP's and test results were reviewed by the inspector:
TP 203/4, "LPI System, ES Test" TP 240/4, " Component Cooling System Functional Test" TP 230/4, "RC Vent and Drain Functional Test" The inspector had no ccaments or questions on these test procedures or test results.
5.
Source Range Instrumentation Response During the initial approach to criticality at Oconee 1, the inverse multiplication plots were not effective in predicting the point the reactor would acheive criticality. To prevent this same situation from occurring at Oconee 2, changes are to be made that will increase the sensitivity of the source range detectors to multiplication neutrons.
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The licensee has indicated that the planned changes will be to:
(a) Add moderntor around each of the source range detectors to increase their effective sensitivity. To preserve overlap between source and intermediate range channels, moderator will also be added around each intermediate range detector.
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RO Rpt. N3. 50-270/73-1 I-3
(b) Eliminate source masking in the reactor by relocating the j
source to a position which is further removed from the source range chambers.
A station problem report has been issued, but the design and installation have not yet been completed or scheduled as yet.
This item will be carried as unresolved item 73-11/1 until the work has been completed.
6.
Status of Regulatory Operations Review of the Preoperational Test Program Test Tests Reviewed Test Results Reviewed Catego ry No.
Percent No.
Percent
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44
53
36
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12
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Preoperational Testing Program Status No.
Percent Tests Completed, Results Approved 205
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Tests Completed, Results not Approved
26 Tests in Progress
9 Test Procedures Approved 302 100
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RO Report No. 50-270/73-11 II-l I
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d 73 DETAILS II Prepared By:
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K. W. Whitt Date Reactor Inspector Facilities Test and Startup Branch Dates of Inspection: Au t 28-31, 1973 Reviewed By: [ [
ef 9/7
C. E. Murphy (Chisf
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Facilities Test and Startup Branch 1.
Individuals Contacted Duke Power Company (DPC)
J. E. Smith - Plant Superintendent J. W. Hampton - Assistant Plant Superintendent R. M. Koehler - Technical Support Engineer O. S. Bradham - Instrument and Control Engineer J. W. Cox - Assistant Plant Engineer P. W. Stephens - Instrument and Control Technician 2.
Witness of Tests Parts of two hot functional tests were witnessed during this inspection.
These tests were TP/0/A/330/3A-1, " Control Rod Drive Rod Drop Time Test," and TP/2/B/600/ll, " Emergency Feed System and GTSG Control Test."
The portions of these tests performed at operating temperature and pressure were observed.
The cold portion of TP/0/A/330/3A-1 was witnessed earlier during phase one of hot functional testing. No deficiencies in test method or results were noted.
3.
Procedure Review The approved procedure and test results of TP/2/A/250/3, " Low
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Pressure Service Water System Functional and Operational Test,"
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l were reviewed.
No specific comments were made on this particular test or procedure, but the following general comment concerning all tests was provided by the inspector at the management interview.
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RO Rpt. No. 50-270/73-11 II-2
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The prerequisites of the test procedures are signed or initialed, but they are not dated.
None of the procedures that have been rev1ewed show two sets of initials which would indicate reverification of the prerequisites.
It was noted that portions of some tests were performed at a given time and the remainder of the test performed after a significant amount of time had elapsed.
Further, the test coordinator's log does not, in most cases, contain entries indicating cocplecion of prerequisite verification.
Therefore, there is no way to determine when the prerequisites were verified and enere doesn't appear to be any existing evidence that any were ever reverified.
In cases where parts of a test are conducted at one time and other parts at another time, it may be desirable to reverify certain prerequisites or other test preparation.
Consideration should be given to the feasibility of identifying a time limit for which a verification is valid after a test interruption.
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A licensee representative stated that an evaluation would be made to determine how best to improve this area of testing.
Station Quality Assurance (QA) Staff
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The review made of the station quality assurance during this inspection indicates that an effective program is being conducted. A number of deficiencies were recorded in several areas as a result of QA audits.
i A brief discussion of audit reports inspected follows;
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a.
Electrical Interlock and Bypass Log An audit of the electrical interlock and bypass log was made by i
the station QA staff on July 17, 1973.
Several deficiencies were noted and recorded in a QA audit report. All of the
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tagged jumpers could not be accounted for and a number of open circuits were observed without tags.
A report containing the
findings of the audit was transmitted by memorandum to the plant superintendent.
On August 14, 1973, the plant superintendent
informed the operations supervisor of the QA audit findings by
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memorandum and instructed him to take action at the earliest possible moment to correct the deficiencies.
The memorandum further instructed the operations supervisor to meet with the j
instrumentation and maintenance supervisors to determine how the
deficiencies were occurring. At the close of the inspection, the corrective action had not been completed._ This item will be carried as UN 73-11/2 and will be reviewed during a future inspection.
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b.
White Tag Log
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The records of a QA audit of the white tag log conducted on
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RO Rpt. No. 50-270/73-11 II-3
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noted and reported to the plant superintendent.
A member of the QA staff indicated that a reaudit was planned for the near future.
c.
Red Tag Audit The review of a QA audit report of the red tag log dated August 2, 1973, indicated that five deficiencies had been noted and reported to the plant superintendent. A me=ber of the QA staff indicated that a reaudit was planned for the near future.
d.
Operator.and Shift Supervisor Log An audit report of the operator and shift supervisor logs covering the period from June 30, 1973, to August 14, 1973, was reviewed by the inspector.
The audit revealed no defic *.encies.
e.
Station PO Drawings An audit of station PO drawings was made on June'7, 11, and 12, 1973.
Several discrepancies were noted, primarily because the latest
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revision of certain drawings were not in use or in the file. A reaudit was ccaducted on July 17, 18, and 19, 1973. Most of the deficiencies resulting from the June audit had been corrected, but several new ones were found.
f.
Field Changes On July 24 and 25, 1973, a member of the station QA staff made an inspection of certain Unit 2 field changes to verify correct wiring and retesting.
The field changes inspected vete:
FC-31 Rev. 2, FC-107, FC-109, FC-110, FC-lll, and FC-ll4.
No deficiencies were noted.
g.
Nuclear Fuel Records
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An audit of nuclear fuel records was conducted on May 18, 1973.
All Unit 2 fuel records were found to be in order.
h.
Periodic Tests An audit was performed in August 1973 by the station QA staff of the operations group periodic tests.
One discrepancy was noted.
This was corrected within one week.
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RO Rpt. No. 50-270/73-11 II-4 1.
Chemistry Department Records An audit of the chemistry department boron sampling and calibration records was performed on August 29, 1973, by the station QA staff.
One discrepancy was noted. A reaudit is scheduled to be conducted within two weeks.
5.
Steam Production Department Quality Assurance Staff The inspector learned that this offsite quality assurance group had made its latest audit of the station proceedings during the week of August 20, 1973. The report of this audit was not available during this inspection.
The areas covered by the audit were nuclear materials, station modifications, tag out logs, emergency procedures, and the controlling procedure for hot functional testing.
Reports which resulted from earlier audits were reviewed.
The primary objective of this review was to determine whether meaningful audits are being conducted by the steam production department quality assurance staff, whether the frequency of the audits meet the requirecent of the Administrative Policy Manual for Operational Quality Assurance, and whether the audits are perfor=ed in accordance with written procedures.
No deficiencies were noted in these areas and the inspector concluded that the DPC offsite quality assurance program is
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functioning in an adequate manner.
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RO Rpt. No. 50-270/73-11 III-1 DETAILS III Prepared by:
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f/7/73 R. C. Lewis, Reactor Inspector Date l
Facilities Operations Branch Dates of Inspection: Augn$t 29-31, 1973 Reviewed by:
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W. C. Seidre,yrief Date Facilities Operations Branch 1.
Individuals Contacted Duke Power Company (DPC)
J. Smith - Plant Superintendent J. Hampton - Assistant Plant Superintendent R. Sharpe - Assistant Plant Engineer L. Schmid - Operating Engineer 2.
General
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The inspection was conducted to review the site records pertaining to the activities of the Station Review Committee (SRC) and the Nuclear Safety Review Committee (NSRC).
3.
SRC The minutes of SRC meetings, reflecting the review activities of the comittee during the period of June 19 through August 28, 1973, were reviewed and compared with the requirements specified in Section 6.1.2.1 of the Technical Specifications and Section 2.6.2.4 of the Administrative Policy Manual for Operational Quality Assurance of Nuclear Stations (APM/NS).
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The records reflect that during the period covered in the review, that the SRC was formally convened 33 times, which exceeds the specified minimum requirement of once/ month. The records also I
reflect that a quorum of members was in attendance at each of the meetings.
Based on the records reviewed, the SRC activit as appear to be
conducted in.accordance with the requirements pecified in Section 6.1.2.1 of the Technical Specifications and Section 2.6.2.4 of the APM/NS.
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4.
NSRC q
f The minutes of the NSRC meetings held during the period of January 30 through August 28, 1973, were reviewed and compared with the require-
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ments specified in Section 6.1.2.2 of the Technical Specifications and Section 2.6.2.2 of the APM/NS. The minutes of the most recent NSRC meeting of August 28-29 had not been prepared at the time of the inspection; however, the proposed agenda for the meeting was reviewed. The NSRC activities prior to January 30, 1973, were a subject cf review during a previous inspection of June 20-21, 1973 (R0 Inspection Report No.
50-269/73-7).
The records reflect that during the period covered in the review that the comittee met with a quorum of members present on March 9 and 20, May 30-31 and August 28-29, 1973.
Comittee reviews included the use of a consultant, Dr. R. L. Murray, and sub-groups assigned specific review responsibilities. Areas reviewed by the comittee included:
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Plant operations since issuance of an operating license (Unit 1)
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Zero power and power ascension testing (Unit 1)
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SRC activities
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Shift Supervisors and operators logs e.
Activities associated with the chemistry laboratory f.
Activities associated with the station quality assurance group.
(Comittee recomended that the Steam Production Department expedite the development of a list that identifies those safety related structures, systems, components, parts and equipment that requires quality assurance.
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Outstanding Items List h.
Unusual conditions, events and abnormal occurrence reports 1.
Feedwater transient problems (Unit 1).
(Comittee recommended that a more extensive analysis of operating incidet.ts.and signifi-cant load changes be conducted.)
j. Technical Specifications violations k.
A proposed Technical Specification change concerning the.aste water collection basin.
(Committee took exception to the proposed
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change and ident ified factors to be considered in resolving
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specific problems associated with the release of radioactive liquids.)
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Oconee problem reports m.
Unit 2 status, staffing, procedures and quality assurance n.
Liquid waste problems o.
Ramifications of valve leaks (liquid, gas and steam)
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RO Rpt. No. 50-270/73-11 III-3
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Two DPC letters dated August 7 and August 27, 1973, concerning the status of recommendations made by the committee, were reviewed. The letter of August 7 shows that of the fif ty-six recommendations made
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by the committee, action had been completed on forty-five of the recomendations. The letter of August 27 reflects that action had been completed on fif ty of the fifty-six items.
Action on the remaining six recommndations was reported to be in various stages of completion.
Based upon the records reviewed, the NSRC activities appear to be in accordance with the requiremnts specified in Section 6.1.2.2 of the Technical Specifications and Section 2.6.2.2 of the APM/NS.
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